DE1031901B - Gas-cooled nuclear reactor - Google Patents
Gas-cooled nuclear reactorInfo
- Publication number
- DE1031901B DE1031901B DES52088A DES0052088A DE1031901B DE 1031901 B DE1031901 B DE 1031901B DE S52088 A DES52088 A DE S52088A DE S0052088 A DES0052088 A DE S0052088A DE 1031901 B DE1031901 B DE 1031901B
- Authority
- DE
- Germany
- Prior art keywords
- moderator
- liquid
- nuclear reactor
- gas
- cooling system
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 238000001816 cooling Methods 0.000 claims description 21
- 239000007788 liquid Substances 0.000 claims description 16
- 230000004888 barrier function Effects 0.000 claims description 9
- 239000000126 substance Substances 0.000 claims description 4
- 230000008929 regeneration Effects 0.000 claims description 3
- 238000011069 regeneration method Methods 0.000 claims description 3
- 239000012530 fluid Substances 0.000 claims description 2
- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 description 5
- 239000002826 coolant Substances 0.000 description 3
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 description 2
- 229910002092 carbon dioxide Inorganic materials 0.000 description 2
- 239000001569 carbon dioxide Substances 0.000 description 2
- 239000000112 cooling gas Substances 0.000 description 2
- 239000000446 fuel Substances 0.000 description 2
- 239000003929 acidic solution Substances 0.000 description 1
- 230000002950 deficient Effects 0.000 description 1
- 230000001419 dependent effect Effects 0.000 description 1
- 238000009792 diffusion process Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 230000005658 nuclear physics Effects 0.000 description 1
- 239000012188 paraffin wax Substances 0.000 description 1
- 125000001997 phenyl group Chemical group [H]C1=C([H])C([H])=C(*)C([H])=C1[H] 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 239000000243 solution Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
- G21C1/16—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
- G21C1/18—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
- G21C1/20—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
DEUTSCHESGERMAN
ßlßUÜTKsKßlßUÜTKsK
DfSSSuTSGHENDfSSSuTSGHEN
fATEHTAMTSSfATEHTAMTSS
Bei gasgekühlten Kernreaktoren mit flüssigem Moderator sind Anordnungen bekanntgeworden, bei denen das Kühlsystem mit dem Reaktorgefäßraum über dem Moderatorspiegel direkt in Verbindung steht, so daß dort derselbe Druck wie im Kühlsystem herrscht. Alle Druckänderungen innerhalb des Kühlsystems teilen sich demnach sofort dem Moderator mit.In gas-cooled nuclear reactors with a liquid moderator, arrangements have become known in which the cooling system is directly connected to the reactor vessel space above the moderator mirror, so that there is the same pressure as in the cooling system. All pressure changes within the cooling system communicate immediately to the moderator.
Dieser Druckausgleich zwischen Moderator und Kühlsystem gestattet, die Wanddicke der Kühlkanäle, die zugleich die Brennstoffelemente enthalten, nach im wesentlichen kernphysikalischen Gesichtspunkten, also möglichst schwach, zu bemessen, da ihnen keine Überdruckbeanspruchungen auftreten können.This pressure equalization between the moderator and the cooling system allows the wall thickness of the cooling channels, which at the same time contain the fuel elements, essentially from the point of view of nuclear physics, that is as weak as possible, to be dimensioned, since no overpressure loads can occur.
Reaktoren dieser Art sind, bei mäßigen Drücken, konstruktiv verhältnismäßig einfach auszubilden und mit bewährten Mitteln auszuführen. Schwierigkeiten sind, jedoch dann zu erwarten, wenn als Kühlmittel Stoffe verwandt werden, die mit der Moderatorflüssigkeit chemisch reagieren oder in dieser in größeren Mengen in Lösung gehen.Reactors of this type are, at moderate pressures, relatively simple to design and construct to be carried out with proven means. Difficulties are to be expected, however, when used as a coolant Substances are used that react chemically with the moderator liquid or in this in larger quantities Quantities go into solution.
Von den bewährten gasförmigen Kühlmitteln trifft dies besonders für Kohlendioxyd zu, das sich im flüssigen Moderator, z. B. in schwerem Wasser, mit druckabhängiger Sättigung löst. Die entstehende saure Lösung ist stark korrosiv. Sie gefährdet nicht nur alle mit der Moderatorflüssigkeit benetzten Bauteile des Reaktors, wie die Druckgefäß- und Kühlkanalwandungen, sondern auch das gesamte Kühlsystem, da der aus dem Moderator herausdiffundierende D2 O-Dampf mit Kohlendioxyd ebenfalls Kohlensäure bildet. Weiterhin wird bei plötzlichen, auch kleinen, Druckabsenkungen gelöstes CO2 aus der Moderatorflüssigbeit ausdampfen, so daß diese aufwallt bzw. überschäumt und unter Umständen in den Kühlkreislauf gerissen wird. Ebenfalls muß vermieden werden, daß Spaltprodukte aus gegebenenfalls defekt gewordenen Brennstoffelementen über den Kühlkreislauf in den Moderator gelangen.Of the proven gaseous coolants, this is particularly true for carbon dioxide, which is in the liquid moderator, z. B. in heavy water, with pressure-dependent saturation dissolves. The resulting acidic solution is highly corrosive. It not only endangers all components of the reactor wetted with the moderator liquid, such as the pressure vessel and cooling channel walls, but also the entire cooling system, since the D 2 O vapor diffusing out of the moderator also forms carbonic acid with carbon dioxide. Furthermore, in the event of sudden, even small, pressure drops, dissolved CO 2 will evaporate from the moderator liquid, so that it billows up or overflows and is possibly torn into the cooling circuit. It must also be avoided that fission products from possibly defective fuel elements get into the moderator via the cooling circuit.
Gemäß der Erfindung werden nur bei Reaktoren, bei denen das Moderatorsystem mit dem Kühlsystem im Druckausgleich steht, die durch die Verwendung nicht inerter Kühlgase entstehenden genannten Schwierigkeiten mit einfachen Mitteln dadurch beseitigt, daß im Reaktor eine flüssige Sperrschicht das Moderatorsystem vom Kühlsystem trennt.According to the invention are only used in reactors in which the moderator system with the cooling system in the pressure equalization is the one mentioned above resulting from the use of non-inert cooling gases Difficulties eliminated by simple means in that a liquid barrier layer in the reactor Separates the moderator system from the cooling system.
Die Zeichnung veranschaulicht schematisch ein Ausführungsbeispiel. The drawing schematically illustrates an embodiment.
Innerhalb des Reaktordruckgefäßes 1 trennt die flüssige Sperrschicht 2 das Moderatorsystem vom Kühlsystem.Inside the reactor pressure vessel 1, the liquid barrier layer 2 separates the moderator system from Cooling system.
Das Moderatorsystem besteht aus der die Kühlkanäle (der Einfachheit halber ist nur einer dargestellt) umgebenden Moderatorfüllung 3 (D2O), der Umwälzleitung 4 mit der Pumpe 5 und der Regene-Gasgekühlter Kernreaktor The moderator system consists of the moderator filling 3 (D 2 O) surrounding the cooling channels (only one is shown for the sake of simplicity), the circulation line 4 with the pump 5 and the rain-gas-cooled nuclear reactor
Anmelder:Applicant:
Siemens-SdiuckertwerkeSiemens-Sdiuckertwerke
Aktiengesellschaft,Corporation,
Berlin und Erlangen,Berlin and Erlangen,
Erlangen, Werner-von-Siemens-Str. 50Erlangen, Werner-von-Siemens-Str. 50
Dr.-Ing. Wolfgang Kahlert, Erlangen,
ist als Erfinder genannt wordenDr.-Ing. Wolfgang Kahlert, Erlangen,
has been named as the inventor
rier- und Kühlanlage 6. Das Kühlsystem innerhalb des Druckgefäßes 1 besteht aus den über die Haltegerüstspalte 7 miteinander in Verbindung stehenden oberen Räumen 8, 9 und den in den unteren Raum 10 einmündenden Kanälen 11,12.rier- and cooling system 6. The cooling system within the pressure vessel 1 consists of the column over the support frame 7 communicating upper rooms 8, 9 and those in the lower room 10 opening channels 11,12.
Wie bereits gesagt, ist der Einfachheit halber nur ein einzelnes Kühlkanalelement dargestellt. Es ist aus einem äußeren Druckrohr 13 und einem inneren Leitrohr 14 aufgebaut, das seinerseits den spaltbaren Kernbrennstoff enthält. An seinem unteren Ende ist das Druckrohr 13 mit dem Zwischenboden 15 des Reaktordruckgefäßes 1 druckdicht verbunden, während es mit seinem oberen Ende im Haltegerüst 16, unter Belassung der bereits genannten Haltegerüstspalte 7, gehaltert ist. Das Druckrohr 13 umschließt koaxial das Leitrohr 14 unter Bildung eines kreisringförmigen äußeren Kanals 11, der gemeinsam mit dem durch das Leitrohr 14 selbst gebildeten Kühlkanal 12 die Verbindung zwischen den oberen und unteren Druckräumen 9, 10 herstellt.As already stated, for the sake of simplicity only a single cooling channel element is shown. It is composed of an outer pressure tube 13 and an inner guide tube 14, which in turn is the fissile Contains nuclear fuel. At its lower end, the pressure pipe 13 is connected to the intermediate floor 15 of the Reactor pressure vessel 1 connected in a pressure-tight manner, while its upper end in the holding frame 16, leaving the above-mentioned supporting scaffold column as it is 7, is held. The pressure tube 13 coaxially surrounds the guide tube 14, forming an annular one outer channel 11, which together with the cooling channel formed by the guide tube 14 itself 12 establishes the connection between the upper and lower pressure chambers 9, 10.
Außerhalb des Druckgefäßes ist das bisher beschriebene Kühlsystem über die an die genannten Druckräume angeschlossene Umwälzleitung 17 mit der Pumpe 18 und dem Wärmetauscher 19 im Kreislauf geschlossen. Als Kühlmittel dient CO2.Outside the pressure vessel, the previously described cooling system is closed in the circuit via the circulation line 17 with the pump 18 and the heat exchanger 19 connected to the aforementioned pressure chambers. CO 2 is used as the coolant.
Zwischen dem Moderator- und Kühlsystem ist als Sperrschichtsubstanz 2 vorzugsweise eine deuterierte, organische Flüssigkeit, z. B. ein Phenyl oder höheres Paraffin, mit Moderator- bzw. Reflektoreigenschaften vorgesehen, die, wie aus der Zeichnung zu ersehen ist, auf der Moderatorflüssigkeit 3 schwimmt. Sie mußThe barrier substance 2 between the moderator and cooling system is preferably a deuterated, organic liquid, e.g. B. a phenyl or higher paraffin, with moderator or reflector properties provided which, as can be seen from the drawing, floats on the moderator liquid 3. She must
809 530/328809 530/328
möglichst wärme- und strahlungsbeständig sein und soll weder mit D2O noch mit CO2 reagieren, oder mischbar sein.be as resistant to heat and radiation as possible and should not react with either D 2 O or CO 2 , or be miscible.
Da sich eine gewisse Vermischung durch Diffusion nie ganz vermeiden läßt, empfiehlt es sich, auch die Sperrflüssigkeit — ähnlich wie die Moderatorflüssigkeit — im Betrieb zu regenerieren.Since a certain mixing by diffusion can never be completely avoided, it is advisable to also use the To regenerate barrier liquid - similar to the moderator liquid - during operation.
Diesem Zweck dient die Regenerieranlage 20, die in den Zug der Umwälzleitung 21 eingeschaltet ist und von der Pumpe 22 mit Sperrflüssigkeit versorgt wird. Die Zu- und Ablauföffnungen der Umwälzleitung 21 am Reaktordruckgefäß 1 sind in bezug auf die Dicke der Sperrflüssigkeitsschicht 2 so angeordnet, daß die Sperrflüssigkeit bei jedem Betriebszustand die öffnungen überdeckt und somit in den Regenerationskreislauf 20, 21, 22 weder Moderatorflüssigkeit noch Kühlgas eindringen kann.The regeneration system 20, which is connected to the train of the circulation line 21, serves this purpose and is supplied with barrier fluid by the pump 22. The inlet and outlet openings of the circulation line 21 on the reactor pressure vessel 1 are arranged in relation to the thickness of the barrier liquid layer 2 so that that the sealing liquid covers the openings in every operating state and thus enters the regeneration circuit 20, 21, 22 neither moderator liquid cooling gas can still penetrate.
Claims (3)
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DES52088A DE1031901B (en) | 1957-01-26 | 1957-01-26 | Gas-cooled nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DES52088A DE1031901B (en) | 1957-01-26 | 1957-01-26 | Gas-cooled nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| DE1031901B true DE1031901B (en) | 1958-06-12 |
Family
ID=7488557
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| DES52088A Pending DE1031901B (en) | 1957-01-26 | 1957-01-26 | Gas-cooled nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| DE (1) | DE1031901B (en) |
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE1128572B (en) * | 1958-08-12 | 1962-04-26 | Siemens Ag | Device for equalizing the operating pressure of coolant and moderator in a nuclear reactor with higher operating pressure |
| US3085959A (en) * | 1959-01-02 | 1963-04-16 | Gen Electric | Liquid moderated vapor superheat reactor |
| DE1149831B (en) * | 1959-06-04 | 1963-06-06 | Commissariat Energie Atomique | Pipe system for removing heat from nuclear reactors |
| US3099616A (en) * | 1958-08-06 | 1963-07-30 | Rolls Royce | Steam cooled reactor and fuel channel |
| DE1208422B (en) * | 1960-03-01 | 1966-01-05 | Commissariat Energie Atomique | Gas- and liquid-tight connection of a fuel pipe with the wall of a nuclear reactor |
| DE1234336B (en) * | 1961-12-20 | 1967-02-16 | Atomic Energy Authority Uk | Boiling water nuclear reactor |
| DE1237232B (en) * | 1961-06-26 | 1967-03-23 | Sulzer Ag | Atomic nuclear reactor with pressure pipes through which reactor coolant flows |
| DE1238113B (en) * | 1959-04-29 | 1967-04-06 | Commissariat Energie Atomique | Nuclear reactor duct |
-
1957
- 1957-01-26 DE DES52088A patent/DE1031901B/en active Pending
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3099616A (en) * | 1958-08-06 | 1963-07-30 | Rolls Royce | Steam cooled reactor and fuel channel |
| DE1128572B (en) * | 1958-08-12 | 1962-04-26 | Siemens Ag | Device for equalizing the operating pressure of coolant and moderator in a nuclear reactor with higher operating pressure |
| US3085959A (en) * | 1959-01-02 | 1963-04-16 | Gen Electric | Liquid moderated vapor superheat reactor |
| DE1238113B (en) * | 1959-04-29 | 1967-04-06 | Commissariat Energie Atomique | Nuclear reactor duct |
| DE1149831B (en) * | 1959-06-04 | 1963-06-06 | Commissariat Energie Atomique | Pipe system for removing heat from nuclear reactors |
| DE1208422B (en) * | 1960-03-01 | 1966-01-05 | Commissariat Energie Atomique | Gas- and liquid-tight connection of a fuel pipe with the wall of a nuclear reactor |
| DE1237232B (en) * | 1961-06-26 | 1967-03-23 | Sulzer Ag | Atomic nuclear reactor with pressure pipes through which reactor coolant flows |
| DE1234336B (en) * | 1961-12-20 | 1967-02-16 | Atomic Energy Authority Uk | Boiling water nuclear reactor |
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